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Publications by Janne Wallenius

Refereegranskade

Artiklar

[1]
F. Dehlin and J. Wallenius, "Activation analysis of the lead coolant in SUNRISE-LFR," Nuclear Engineering and Design, vol. 414, 2023.
[2]
F. Dehlin, J. Wallenius and S. Bortot, "An analytic approach to the design of passively safe lead-cooled reactors (vol 169, 108971, 2022)," Annals of Nuclear Energy, vol. 181, 2023.
[5]
C. Reale Hernandez, J. Wallenius and J. Luxat, "Simulation of a loss of flow transient of a small Lead-Cooled reactor using a CFD-Based model," Nuclear Engineering and Design, vol. 412, 2023.
[6]
Y. Mishchenko et al., "Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution," Nuclear Materials and Energy, vol. 35, 2023.
[8]
F. Dehlin, J. Wallenius and S. Bortot, "An analytic approach to the design of passively safe lead-cooled reactors," Annals of Nuclear Energy, vol. 169, pp. 108971-108971, 2022.
[9]
J. Wallenius, "An improved correlation for gas release from nitride fuels," Journal of Nuclear Materials, vol. 558, 2022.
[10]
D. R. Costa et al., "Coated ZrN sphere-UO2 composites as surrogates for UN-UO2 accident tolerant fuels," Journal of Nuclear Materials, vol. 567, pp. 153845, 2022.
[11]
C. R. Hernandez et al., "Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor," Nuclear Engineering and Design, vol. 392, pp. 111773, 2022.
[13]
[16]
Y. Mishchenko et al., "Design and fabrication of UN composites : From first principles to pellet production," Journal of Nuclear Materials, vol. 553, pp. 153047, 2021.
[19]
[20]
J. Wallenius, "Anomalous reactivity swing in the 238U-233U system," Annals of Nuclear Energy, vol. 139, 2020.
[21]
C. Reale Hernandez, J. Wallenius and J. Luxat, "Dynamic sensitivity and uncertainty analysis of a small lead cooled reactor," Annals of Nuclear Energy, vol. 144, 2020.
[22]
C. Ekberg et al., "Fuel fabrication and reprocessing issues : the ASGARD project," EPJ Nuclear Sciences & Technologies., vol. 6, 2020.
[23]
D. R. Costa et al., "UN microspheres embedded in UO2 matrix : An innovative accident tolerant fuel," Journal of Nuclear Materials, vol. 540, 2020.
[24]
J. Wallenius and S. Bortot, "A new paradigm for breeding of nuclear fuel," Annals of Nuclear Energy, vol. 133, pp. 816-819, 2019.
[25]
J. Wallenius, "Maximum efficiency nuclear waste transmutation," Annals of Nuclear Energy, vol. 125, pp. 74-79, 2019.
[26]
J. Wallenius and S. Bortot, "A small lead-cooled reactor with improved Am-burning and non-proliferation characteristics," Annals of Nuclear Energy, vol. 122, pp. 193-200, 2018.
[27]
J. Wallenius et al., "Design of SEALER, a very small lead-cooled reactor for commercial power production in off-grid applications," Nuclear Engineering and Design, vol. 338, pp. 23-33, 2018.
[28]
K. Johnson et al., "Oxidation of accident tolerant fuel candidates," Journal of Nuclear Science and Technology, vol. 54, no. 3, pp. 280-286, 2017.
[29]
E. Bubelis et al., "System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions," Nuclear Engineering and Design, vol. 320, pp. 325-345, 2017.
[30]
K. D. Johnson et al., "Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications," Journal of Nuclear Materials, vol. 477, pp. 18-23, 2016.
[31]
K. D. Johnson et al., "Spark plasma sintering and porosity studies of uranium nitride," Journal of Nuclear Materials, vol. 473, pp. 13-17, 2016.
[32]
S. Bortot, E. Suvdantsetseg and J. Wallenius, "BELLA : a multi-point dynamics code for safety-informed design of fast reactors," Annals of Nuclear Energy, vol. 85, pp. 228-235, 2015.
[33]
P. R. Hania et al., "Irradiation and post-irradiation examination of uranium-free nitride fuel," Journal of Nuclear Materials, vol. 466, pp. 597-605, 2015.
[34]
E. Suvdantsetseg and J. Wallenius, "An assessment of prompt neutron reproduction time in a reflector dominated fast critical system : ELECTRA," Annals of Nuclear Energy, vol. 71, pp. 159-165, 2014.
[35]
P. Malkki et al., "Manufacture of fully dense uranium nitride pellets using hydride derived powders with spark plasma sintering," Journal of Nuclear Materials, vol. 452, no. 1-3, pp. 548-551, 2014.
[36]
Y. Zhang and J. Wallenius, "Upper limits to americium concentration in large sized sodium-cooled fast reactors loaded with metallic fuel," Annals of Nuclear Energy, vol. 70, pp. 180-187, 2014.
[37]
J. Zakova and J. Wallenius, "Multirecycling of Pu, Am and Cm in BWR," Annals of Nuclear Energy, vol. 58, pp. 255-267, 2013.
[38]
E. Suvdantsetseg, J. Wallenius and S. Bortot, "Optimization of the reactivity control drum system of ELECTRA (vol 252C, pg 209, 2012)," Nuclear Engineering and Design, vol. 255, pp. 376-376, 2013.
[39]
Y. Zhang, J. Wallenius and M. Jolkkonen, "Transmutation of americium in a large sized sodium-cooled fast reactor loaded with nitride fuel," Annals of Nuclear Energy, vol. 53, pp. 26-34, 2013.
[40]
J. Wallenius, E. Suvdantsetseg and A. Fokau, "Electra : European Lead-Cooled Training Reactor," Nuclear Technology, vol. 177, no. 3, pp. 303-313, 2012.
[41]
J. Zakova and J. Wallenius, "Fuel residence time in BWRs with nitride fuels," Annals of Nuclear Energy, vol. 47, pp. 182-191, 2012.
[42]
E. Suvdantsetseg, J. Wallenius and S. Bortot, "Optimization of the reactivity control drum system of ELECTRA," Nuclear Engineering and Design, vol. 252, no. 1, pp. 209-214, 2012.
[43]
J. Wallenius, "Physics of Americium transmutation," Nuclear Engineering and Technology, vol. 44, no. 2, pp. 199-206, 2012.
[44]
M. Tesinsky, Y. Zhang and J. Wallenius, "The impact of americium on the ULOF and UTOP transients of the European Lead-cooled SYstem (ELSY)," Annals of Nuclear Energy, vol. 47, pp. 104-109, 2012.
[45]
M. Tesinsky et al., "The impact of americium on transients in the European Lead-cooled SYstem ELSY loaded with nitride fuel," Annals of Nuclear Energy, vol. 50, pp. 56-62, 2012.
[46]
J. Wallenius, N. Sandberg and K. Henriksson, "Atomistic modelling of the Fe-Cr-C system," Journal of Nuclear Materials, vol. 415, no. 3, pp. 316-319, 2011.
[47]
Y. Zhang et al., "Physics and safety studies of a compact ADS design loaded with nitride fuel," Annals of Nuclear Energy, vol. 38, no. 11, pp. 2350-2355, 2011.
[48]
J. Zakova and J. Wallenius, "Void reactivity feedback in BWRs with MA bearing MOX fuels," Annals of Nuclear Energy, vol. 38, no. 9, pp. 1968-1977, 2011.
[49]
A. Fokau et al., "A source efficient ADS for minor actinides burning," Annals of Nuclear Energy, vol. 37, no. 4, pp. 540-545, 2010.
[50]
Y. Zhang, J. Wallenius and A. Fokau, "Transmutation of americium in a medium size sodium cooled fast reactor design," Annals of Nuclear Energy, vol. 37, no. 5, pp. 629-638, 2010.
[51]
M. Pukari et al., "Vacancy formation and solid solubility in the U-Zr-N system," Journal of Nuclear Materials, vol. 406, no. 3, pp. 351-355, 2010.
[53]
W. Maschek et al., "Accelerator driven systems for transmutation : Fuel development, design and safety," Progress in nuclear energy (New series), vol. 50, no. 2-6, pp. 333-340, 2008.
[54]
K. O. E. Henriksson, N. Sandberg and J. Wallenius, "Carbides in stainless steels : Results from ab initio investigations," Applied Physics Letters, vol. 93, no. 19, 2008.
[55]
N. Sandberg, K. O. E. Henriksson and J. Wallenius, "Carbon impurity dissolution and migration in bcc Fe-Cr : First-principles calculations," Physical Review B. Condensed Matter and Materials Physics, vol. 78, no. 9, 2008.
[56]
J. Wallenius and D. Westlén, "Hafnium clad fuels for fast spectrum BWRs," Annals of Nuclear Energy, vol. 35, no. 1, pp. 60-67, 2008.
[57]
L. Malerba, A. Caro and J. Wallenius, "Multiscale modelling of radiation damage and phase transformations : The challenge of FeCr alloys," Journal of Nuclear Materials, vol. 382, no. 2-3, pp. 112-125, 2008.
[58]
P. Olsson, C. Domain and J. Wallenius, "Ab initio study of Cr interactions with point defects in bcc Fe," Physical Review B. Condensed Matter and Materials Physics, vol. 75, no. 1, pp. 014110, 2007.
[59]
V. Pontikis, V. Russier and J. Wallenius, "An analytic n-body potential for bcc iron," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 255, no. 1, pp. 37-40, 2007.
[60]
L. Malerba et al., "Modelling of radiation damage in Fe-Cr alloys," Journal of ASTM International, vol. 4, no. 6, 2007.
[61]
J. Wallenius et al., "Simulation of thermal ageing and radiation damage in Fe-Cr," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 255, no. 1, pp. 68-74, 2007.
[62]
N. Juslin et al., "Simulation of threshold displacement energies in FeCr," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 255, no. 1, pp. 75-77, 2007.
[63]
K. Tucek et al., "Studies of an accelerator-driven transuranium burner with hafnium-based inert matrix fuel," Nuclear Technology, vol. 157, no. 3, pp. 277-298, 2007.
[64]
D. A. Terentyev et al., "Displacement cascades in Fe-Cr : A molecular dynamics study," Journal of Nuclear Materials, vol. 349, no. 1-2, pp. 119-132, 2006.
[65]
D. Terentyev et al., "Effect of the interatomic potential on the features of displacement cascades in alpha-Fe : A molecular dynamics study," Journal of Nuclear Materials, vol. 351, no. 03-jan, pp. 65-77, 2006.
[66]
P. Olsson, I. A. Abrikosov and J. Wallenius, "Electronic origin of the anomalous stability of Fe-rich bcc Fe-Cr alloys," Physical Review B. Condensed Matter and Materials Physics, vol. 73, no. 10, pp. 104416, 2006.
[67]
J. Wallenius, S. Pillon and L. Zaboudko, "Fuels for accelerator-driven systems," Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 562, no. 2, pp. 625-629, 2006.
[68]
K. Nordlund, J. Wallenius and L. Malerba, "Molecular dynamics simulations of threshold displacement energies in Fe," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 246, no. 2, pp. 322-332, 2006.
[69]
D. Westlén and J. Wallenius, "On TiN-particle fuel based helium-cooled transmutation systems," Annals of Nuclear Energy, vol. 33, no. 16, pp. 1322-1328, 2006.
[70]
S. Pillon and J. Wallenius, "Oxide and nitride TRU fuels : Lessons drawn from the CONFIRM and FUTURE projects of the 5th European Framework Program," Nuclear science and engineering, vol. 153, no. 3, pp. 245-252, 2006.
[71]
P. Seltborg and J. Wallenius, "Proton source efficiency for heterogeneous distribution of actinides in the core of an accelerator-driven system," Nuclear science and engineering, vol. 154, no. 2, pp. 202-214, 2006.
[72]
M. Eriksson et al., "Inherent Safety of Fuels for Accelerator-driven Systems," Nuclear Technology, vol. 151, no. 3, pp. 314-333, 2005.
[73]
D. Westlén and J. Wallenius, "Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation," Nuclear Technology, vol. 154, no. 1, pp. 41-51, 2005.
[74]
J. Wallenius and M. Eriksson, "Neutronics of minor-actinide burning accelerator-driven systems with ceramic fuel," Nuclear Technology, vol. 152, no. 3, pp. 367-381, 2005.
[75]
P. Olsson et al., "Two-band modeling of alpha-prime phase formation in Fe-Cr," Physical Review B. Condensed Matter and Materials Physics, vol. 72, no. 21, pp. 1-6, 2005.
[76]
K. Tucek, J. Wallenius and W. Gudowski, "Coolant void worth in fast breeder reactors and accelerator-driven transuranium and minor-actinide burners," Annals of Nuclear Energy, vol. 31, no. 15, pp. 1783-1801, 2004.
[77]
J. Wallenius et al., "Development of an EAM potential for simulation of radiation damage in Fe-Cr alloys," Journal of Nuclear Materials, vol. 329-33, pp. 1175-1179, 2004.
[78]
J. Wallenius et al., "Modeling of chromium precipitation in Fe-Cr alloys," Physical Review B Condensed Matter, vol. 69, pp. 094103, 2004.
[79]
L. Malerba et al., "Molecular dynamics simulation of displacement cascades in Fe-Cr alloys," Journal of Nuclear Materials, vol. 329-33, pp. 1156-1160, 2004.
[80]
M. Jolkkonen, M. Streit and J. Wallenius, "Thermo-chemical modelling of uranium-free nitride fuels," Journal of Nuclear Science and Technology, vol. 41, no. 4, pp. 457-465, 2004.
[81]
P. Olsson et al., "Ab initio formation energies of Fe-Cr alloys," Journal of Nuclear Materials, vol. 321, no. 1, pp. 84-90, 2003.
[82]
E. Lindroth, J. Wallenius and S. Jonsell, "Decay rates of excited muonic molecular ions," Physical Review A. Atomic, Molecular, and Optical Physics, vol. 68, no. 3, 2003.
[83]
P. Seltborg et al., "Definition and application of proton source efficiency in accelerator driven systems," Nuclear science and engineering, vol. 145, no. 3, pp. 390-399, 2003.
[84]
J. Wallenius, "Neutronic aspects of inert matrix fuels for application in ADS," Journal of Nuclear Materials, vol. 320, no. 02-jan, pp. 142-146, 2003.
[85]
J. Wallenius et al., "Application of burnable absorbers in an accelerator-driven system," Nuclear science and engineering, vol. 137, no. 1, pp. 96-106, 2001.
[86]
J. Wallenius et al., "Muonic atom deexcitation via formation of metastable molecular states in light of experimental verification," Hyperfine Interactions, vol. 138, no. 04-jan, pp. 285-288, 2001.
[87]
W. Gudowski et al., "Review of the European project - Impact of Accelerator-Based Technologies on Nuclear Fission Safety (IABAT)," Progress in nuclear energy (New series), vol. 38, no. 1-2, pp. 135-151, 2001.

Konferensbidrag

[88]
I. Morelová et al., "IAEA'S Coordinated Research Projects on Thermal Hydraulics of Fast Reactors," in Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023, 2023.
[89]
D. R. Costa et al., "Coated UN microspheres embedded in UO2 matrix as an innovative advanced technology fuel: Early progress," in TopFuel 2021 Light Water Reactor Fuel Performance Conference, Santander, Spain, October 24-28, 2021., 2021.
[90]
J. Wallenius, S. Bortot and I. Mickus, "Unprotected transients in sealer : A small lead-cooled reactor for commercial power production in Arctic Regions," in International Conference on Physics of Reactors, PHYSOR 2018 : Reactor Physics Paving the Way Towards More Efficient Systems, 2018, pp. 1437-1448.
[91]
J. Wallenius and M. Hussein, "Uranium nitride fuels for application in CANDU reactors," in International Conference on Physics of Reactors, PHYSOR 2018 : Reactor Physics Paving the Way Towards More Efficient Systems, 2018, pp. 3603-3611.
[92]
K. Lambrinou et al., "Corrosion-resistant ternary carbides for use in heavy liquid metal coolants," in Ceramic Engineering and Science Proceedings, 2016, pp. 19-34.
[93]
F. Delage et al., "ADS fuel developments in Europe : Results from the EUROTRANS integrated project," in Energy Procedia, 2011, pp. 303-313.
[94]
G. J. Ackland, D. J. Hepburn and J. Wallenius, "Interatomic forces for transition metals including magnetism," in 139th Annual Meeting & Exhibition - Supplemental Proceedings, Vol 2 : Materials Characterization, Computation And Modeling And Energy, 2010, pp. 85-92.

Icke refereegranskade

Böcker

[95]
J. Wallenius, Transmutation of Nuclear Waste. 400th ed. Märsta : Blykalla böcker och spel, 2011.

Kapitel i böcker

[96]
J. Wallenius, "Micro-reactors," in Encyclopedia of Nuclear Energy, : Elsevier BV, 2021, pp. 749-756.
[97]
J. Wallenius, "Nitride Fuels," in Comprehensive Nuclear Materials: Second Edition, : Elsevier BV, 2020, pp. 88-101.

Patent

Patent

[98]
M. Jolkkonen, K. Johnson and J. Wallenius, "Fuel for water-cooled nuclear reactors," WIPO (PCT) WO2016122374A1, 2016.
[99]
J. Wallenius, M. Jolkkonen and M. Radwan, "Nitride nuclear fuel and method for its production," , 2010.
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2024-04-12 00:24:17